MODELING OF THE SUB-SUFACE REDUCING ENVIRONMENT OF THE Z-AREA SALTSTONE DISPOSAL FACILITY AT THE SAVANNAH RIVER SITE [electronic resource]
Low-level radioactive liquid wastes at the U.S. Department of Energy Savannah River Site are treated by mixing the wastes with Saltstone grout to generate the Saltstone waste form that is poured into the concrete vaults for long-term disposal. The formula for Saltstone includes ≈25 wt% slag to creat...
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Online Access |
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| Format: | Government Document Electronic eBook |
| Language: | English |
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Washington, D.C. : Oak Ridge, Tenn. :
United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
2006.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a MODELING OF THE SUB-SUFACE REDUCING ENVIRONMENT OF THE Z-AREA SALTSTONE DISPOSAL FACILITY AT THE SAVANNAH RIVER SITE |h [electronic resource] |
| 260 | |a Washington, D.C. : |b United States. Dept. of Energy ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 2006. | ||
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| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 12/18/2006. | ||
| 500 | |a "wsrc-sti-2006-00367" | ||
| 500 | |a SCS Spring Simulation MultiConference. | ||
| 500 | |a Hang, T; Daniel Kaplan, D. | ||
| 520 | 3 | |a Low-level radioactive liquid wastes at the U.S. Department of Energy Savannah River Site are treated by mixing the wastes with Saltstone grout to generate the Saltstone waste form that is poured into the concrete vaults for long-term disposal. The formula for Saltstone includes ≈25 wt% slag to create a reducing environment for mitigating the sub-surface transport of several radionuclides, including Tc-99. A two-dimensional reactive transport model was developed to estimate how long the Z-Area Saltstone will maintain a reducing environment, and therefore its ability to request Tc-99. The model predicted that ≈16% of the Saltstone reduction capacity would be consumed after 213,000 years. Independent calculations published by other researchers yielded nearly identical results. The general modeling approach and the study results are presented in this paper. | |
| 536 | |b DE-AC09-96SR18500. | ||
| 650 | 7 | |a Transport. |2 local. | |
| 650 | 7 | |a Grouting. |2 local. | |
| 650 | 7 | |a Capacity. |2 local. | |
| 650 | 7 | |a Savannah River Plant. |2 local. | |
| 650 | 7 | |a Slags. |2 local. | |
| 650 | 7 | |a Waste Forms. |2 local. | |
| 650 | 7 | |a Concretes. |2 local. | |
| 650 | 7 | |a Simulation. |2 local. | |
| 650 | 7 | |a Wastes. |2 local. | |
| 650 | 7 | |a Radioisotopes. |2 local. | |
| 650 | 7 | |a Liquid Wastes. |2 local. | |
| 650 | 7 | |a Management Of Radioactive Wastes, And Non-radioactive Wastes From Nuclear Facilities. |2 edbsc. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Savannah River Site. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
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